Argonne National Laboratory – West

SEC Petition Evaluation Report

SEC00224 

Timothy D. Taulbee, PhD, CHP

Research Health Scientist

National Institute for Occupational Safety and Health

Division of Compensation Analysis and Support
ORAU Evaluation Team

 W. Mitch Findley – Team Leader (EBR-I, ZPR-III)

 Brian Gleckler (EBR-II, FCF, HFEF)

 Jason Davis (ZPPR, TREAT, L&O) 

 J. Michael Mahathy (BORAX, AFSR)

 Data Capture Support Team

 William Connell

 Jennifer Warner

 Art Gutzman

 Guy Babin

Division of Compensation Analysis and Support
Petition Overview

 Petition Received on December 4, 2014

 Petition Qualified on March 13, 2015

 Notification to Petitioner and ABRWH in June 2015 that

NIOSH would exceed 180 day deadline due to site 

complexity and need for multiple data capture efforts 

onsite.

 Further delay in September 2015 due to dosimetry 

records issue between ANL-E and INL 

 Evaluation Report sent to ABRWH on February 24, 2016

 Evaluation Report sent to Petitioner March 8, 2016

Division of Compensation Analysis and Support
Proposed Class

All employees of the Department of Energy, its 

predecessor agencies, and their contractors and 

subcontractors who worked at the Argonne National 

Laboratory-West between April 10, 1951 and 

December 31, 1957 for a number of work days 

aggregating at least 250 work days, occurring either 

solely under this employment, or in combination with 

work days within the parameters established for one 

or more other classes of employees in the Special 

Exposure Cohort.

Division of Compensation Analysis and Support
ANL-W

Division of Compensation Analysis and Support

Operating Areas (green)

 West Area 

 1951-1967

 EBR-I, ZPR-III, AFSR, 

BORAX (I-V)

 East Area 

 1958 – 2005

 EBR-II, ZPPR, TREAT, 

FCF, HFEF-N, L&O
ANL-W Major Operating Facilities

West Site

1. Experimental Breeder Reactor #1 (EBR-I)

2. Zero Power Reactor #3 (ZPR-III) 

3. BOiling water ReActor eXperiments (BORAX)

4. Argonne Fast Source Reactor (AFSR)

East Site

5. Transient REActor Tests (TREAT)

6. Experimental Breeder Reactor #2 (EBR-II)

7. Fuel Cycle Facility (FCF) later (HFEF-S)

8. Hot Fuel Examination Facility (HFEF-N)

9. Laboratory and Office Building (L&O)

10. Zero Power Plutonium Reactor (ZPPR)

Division of Compensation Analysis and Support
West Area (1951-1967)

Division of Compensation Analysis and Support
Experimental Breeder Reactor #1

 December 1951

First reactor to generate 

electric power 

 In 1953 analysis of EBR-I 

fuel and blanket 

demonstrated the breeding 

concept and produced 

slightly more fuel than was 

used

 November 1962

First reactor to generate 

electricity using a 

plutonium core

Division of Compensation Analysis and Support
EBR-I Radiological Exposures

 Primary exposure was Mixed Fission Products (MFP)

 Limited actinide exposure due to cladding of both the 

fuel and blanket

 Blanket brick rupture - April 1955

 Plutonium bioassay for 16 workers week after incident

 No other Pu bioassay has been found although monthly 

reports have indicated a couple of other instances when 

blanket bricks ruptured. 

Division of Compensation Analysis and Support
EBR-1 Core Melt

 Core melted down in 

November 1955 during 

reactivity test.

 Building was evacuated and 

shutdown for several days.

 Special coffin built to remove 

core and send it to ANL-E for 

analysis.

 Uranium and mixed fission 

product bioassay for some 

workers.

Division of Compensation Analysis and Support

Stacy, 2000
BOiling water ReActor eXperiments

(BORAX) #1

 Built in 1953

 Determine the self-limiting 

characteristics of water- cooled reactors 

 Small reactor in a tank of 

water

 Could only be used during 

the summer months 

because the reactor was 

not housed

Division of Compensation Analysis and Support
BORAX #1

 Reactor tank filled 

with water and 

brought to critical 

and boiling 

conditions

 Test reactivity and 

effects by quick 

removal of controls

 Water would blow 

out of reactor like a 

small geyser

Division of Compensation Analysis and Support

Haroldsen, 2008

Haroldsen, 2008
BORAX #1

 Final test July 1954 

 Deliberate 

introduction of large 

reactivity

 Reactor exploded 

due to rapid steam 

buildup.

 Fuel, control rods, 

and other activated 

equipment scattered 

across the area.

Division of Compensation Analysis and Support

http://www.ne.anl.gov/About/reactors/lwr3.shtml (2016)
BORAX #1 - Recovery

 Interview with worker who participated in the test 

and gave a detailed account of the event. 

 Photographer had to go in to get the film of the 

explosion. He then had to be decontaminated from 

fresh mixed fission products.

 The following days were spent rotating workers into pit 

where the reactor was to recover gold foils so that they 

could determine the power the reactor attained before 

exploding.

 Basically workers were standing in the remains of 

the reactor digging and sorting through mixed 

fission and activation product sludge. 

Division of Compensation Analysis and Support
BORAX #2

 Boiling Water 

Reactor (BWR) tests 

continuation.

 No turbine-generator 

thus no electrical 

generation.

 March 1955 turbine 

added to 

demonstrate 

contamination would 

not be a problem.

Division of Compensation Analysis and Support

http://www.ne.anl.gov/About/reactors/lwr3.shtml (2016)
BORAX #3 (BORAX #2 with Turbine)

 July 1955 supplied the first 

atomic generated power to 

the city of Arco, Idaho.

Division of Compensation Analysis and Support
External and Internal Dosimetry

 ANL-E reported that they believed they did not have 

any ANL-W dosimetry

 INL reported that they believed they had all of the 

ANL-W dosimetry

 Blind test of 50 cases with some known to have 

worked at ANL-E before going to ANL-W and some 

cases known to have only worked at ANL-W

 Both have parts of early dosimetry but neither appears 

to be complete. 

Division of Compensation Analysis and Support
Incomplete External Monitoring Data 

(1951-1957)

 ANL-E in Illinois 

 Individual dosimeter readings for most (not all) of test case 

workers from 1952 through March 1955

 Idaho National Laboratory (INL)

 Annual summaries from 1952 through 1957 for ANL-W 

workers who were still employed in 1958

 De-identified individual dosimeter readings (1954 - 1957)

 Individual dosimeter readings (1958 – 2005) 

 Potential external dosimetry data gap from 1955 

through 1958 if a worker terminated before 1958.

Division of Compensation Analysis and Support
EBR-I Complex Internal Monitoring

 Bioassay monitoring campaign in June 1952 for 

gross alpha and uranium 

 Extremely limited (very few samples) for mixed 

fission product bioassay prior to 1958.

 No mixed fission product bioassay for people known to 

have worked during BORAX-1 recovery in 1954

 Neither ANL-E nor INL provided bioassay in 1955 

(rupture brick and core melt) for test cases known 

to have been involved.

 Bioassay records were located in other radiological boxes

Division of Compensation Analysis and Support
EBR-I Radiological Monitoring (Air)

 No air monitoring data available in 1951-1954 and 

1957.

 Limited 1955 and 1956 air monitoring data. Files 

appears to be an individual Health Physicists copy 

not the original and likely not complete. When 

available air monitoring data generally limited to 

reactor top, main floor, and basement. 

 After 1958, bioassay data available as well as 

extensive air monitoring and smear data indicating 

clean areas or very low level contamination. 

Occasional hot spots identified on routine surveys 

and cleanup thereafter.

Division of Compensation Analysis and Support
EBR-I, BORAX Summary

 Without mixed fission product exposure 

information (bioassay or air monitoring), cannot 

estimate mixed fission product dose and associated 

actinide exposures from EBR-I and BORAX.

 Potentially incomplete external monitoring data for 

workers at the West site (EBR-I, BORAX)) who 

terminated before 1958. 

 Recommend adding class to Special Exposure 

Cohort (SEC) due to inadequate mixed fission 

product monitoring and potentially incomplete 

external monitoring data prior to 1958.

Division of Compensation Analysis and Support
Zero Power Reactor - III

 Design was two 

halves of a 

reactor loaded 

with fuel drawers 

of various 

configurations.

 One half is 

moved towards 

other to achieve 

criticality.

Division of Compensation Analysis and Support

http://www.ne.anl.gov/About/reactors/frt.shtml (2016)
Zero Power Reactor - III

 Initial drawers were uranium, 

depleted uranium, enriched 

uranium, sodium, etc...

Division of Compensation Analysis and Support
ZPR-III Radiological Exposures

 Minimal fission product exposure as the reactor 

was operated at very low power

 Some potential for uranium exposure in handling 

fuel plates and pins that were only painted and not 

clad

 Exposure to plutonium was very well controlled 

and caution was used. Verification that cladding 

was intact performed through multiple 

contamination surveys of plutonium fuel plates. 

Division of Compensation Analysis and Support
East Area (modern view)

Division of Compensation Analysis and Support
Transient REActor Tests (TREAT)

 Started Operation 2/59

 Study fuel meltdowns

 Metal-water reactions and 

interactions 

 Transient behavior of fuels in

high-temperature systems

 Neutron radiography

 Remote operation during 

some transients

 Health Physics monitored and 

cleared building for reentry

Division of Compensation Analysis and Support

http://www.ne.anl.gov/About/reactors/frt.shtml (2016)
Experimental Breeder Reactor II

 Originally designed 

and operated with 

emphasis on 

demonstrating a 

complete breeder- reactor power plant 

with onsite 

reprocessing of 

metallic fuel. 

 Dry Critical 9/61

 Sodium cooled 

reactor, “Wet 

Critical” 11/63

Division of Compensation Analysis and Support

ANL-PIO, undated, early 1960s 
EBR-II Radiological Exposures

 External dose – some but not tremendous as design 

(sodium) tends to keep fission products (including 

volatiles like iodine) bound in system/pool and away 

from workers while they decay. Some areas did have 

moderate levels of exposure. 

 Workers expressed concern with exposure while 

cleaning and removing the dross (oxidized tin-bismuth) 

from the rotating plugs used to move fuel. This area 

was right above the argon blanket gas. Exposure is 

primarily due to activation products but some mixed 

fission products. 

Division of Compensation Analysis and Support
EBR-II Radiological Monitoring

 Internal dose primarily beta/gamma. No actinide 

exposures without beta/gamma exposure. Thus 

beta/gamma can be used to bound actinides. 

 Urinalysis and extensive whole body counting (WBC) of 

the workforce. Monthly reports indicate approximately 

30-35 workers per month. (360-420 per year).

 Workplace monitoring

 Continuous air monitors throughout building and on 

exhaust.

 Routine surveys of the building included checks for alpha 

contamination. 

Division of Compensation Analysis and Support
Fuel Cycle Facility (FCF) Operations

 Operations from 

1964-1969 

demonstrated a 

fully functional 

reprocessing facility.

 Air cell mostly for 

transfer of materials

 Argon Cell (hot cell 

filled with Argon)

 Outer rooms initially 

for support then 

cold line

Division of Compensation Analysis and Support
FCF Radiological Exposures

 Argon Cell NOT entered until 1978. Extensive monitoring 

during this refurbishment work. – Health Physics

 Air Cell entries were infrequent (according to interviews)

 Effort to decontaminate before entry. 

 Health physics monitoring before, during and after entry.

 Usually air samples were taken during work in cell. 

 Beta/gamma contamination levels much higher than alpha 

and dominated exposure.

 Sub-cell work in basement health physics always 

accompanied operations and surveyed before and after 

work. 

Division of Compensation Analysis and Support
FCF Radiological Monitoring

 Urine bioassay and whole body counts for workers 

at FCF

 Routine air monitoring in the passageway, main 

floor, basement, and roof.

 Routine radiation and contamination surveys 

(including alpha) throughout the building. 

 For most of the work, beta/gamma always present 

thus actinide exposures can be bounded with ratio 

as indicated in Technical Basis Document (TBD).

Division of Compensation Analysis and Support
FCF Rad Exposure - Exceptions

 Work in the mold preparation room 25 involving 

thoria prior to 1967.

 Air monitoring and routine alpha contamination surveys 

available in room 25

 Will develop an exposure model using either air samples 

or 10% MPC

 Cold Line 

 Continuous low level alpha contamination from uranium 

in several of the outer loop rooms.

 Most smears are less than 100 dpm/100cm2 but some smear 

results can be as high as few thousand dpm. 

 Air sample data is available and intent is to use air data for 

exposure model. 

Division of Compensation Analysis and Support
Hot Fuel Examination Facility (HFEF-N)

 Operation 

12/1972 - Decon Cell

3/1975 - Main Cell

 Examine hot or

irradiated fuels

 Larger more 

versatile facility

than FCF

 1978 Neutron 

RADiography

Facility (NRAD)

Division of Compensation Analysis and Support

https://www.inl.gov/wp-content/uploads/2014/10/HFEF-Cell-D12772.jpg
HFEF-N Radiological Monitoring

 Workers on routine whole body count schedule.

 Ratio method can be used to determine actinide 

exposure

 Fixed air sampling system (FASS) installed in 

1976, (Health Physics) however, routine air sampling 

as early as August 1972

 Routine radiation and contamination surveys 

were conducted.

Division of Compensation Analysis and Support
Laboratory and Office Building (L&O)

 Started operation 1961

 Analytical laboratories which contained some 

gloveboxes supported EBR-II and FCF operations.

 Chemical, metallurgy, and radiological analysis of 

coolant, fuels, air, etc... 

 Hot cells “Junior Caves” would process small 

samples from fuel cycle. 

 Vaults would receive and store some fresh 

enriched fuel 

Division of Compensation Analysis and Support
L&O Radiological Exposure and 

Monitoring

 Most exposure was beta/gamma, however due 

to the nature of the activities (chemical 

separations on samples), some potential for 

alpha exposure without or limited beta/gamma.

 Highest risk areas were the laboratories and 

junior caves. However there is extensive 

radiological monitoring throughout the timeline. 

 Routine air monitoring and contamination surveys in 

junior cave area and analytical laboratories. 

Division of Compensation Analysis and Support
Zero Power Plutonium Reactor (ZPPR)

 Started operation 1969

 Purpose was to construct 

assemblies that closely 

resembled various fast 

reactor designs.

 Design much like ZPR-III

(moveable halves) except 

much larger and versatile.

Division of Compensation Analysis and Support

https://www.flickr.com/photos/argonne/8167913135 (2016)
ZPPR Radiological Exposures

 As with ZPR-III, minimal fission product exposure 

as the reactor was operated at very low power

 Some potential for uranium exposure in handling 

fuel plates and pins that were only painted and not 

clad

 Exposure to plutonium was again very well 

controlled and caution was used (cladding and 

verification thereof)

 When a fuel plate was monitored and found to 

have contamination or if there was some type of 

mechanical defect with cladding it was bagged and 

logged as a suspect fuel element

Division of Compensation Analysis and Support
ZPPR Radiological Monitoring

 Five continuous air monitors

 Each half of the reactor (2), reactor cell near entrance, 

loading workroom, and storage vault

 Alpha contamination does not seem to be tolerated. 

 Routine smear data indicates relatively low levels of 

alpha contamination

 Air samples were counted allowing for radon decay 

until alpha activity was less than 10% MPC.

 Actinide doses can be bounded based on 10% of MPC.

Division of Compensation Analysis and Support
Feasibility of Dose Reconstruction

 Up until 1958 the West site (EBR-I complex) was 

determined to be infeasible due to limited mixed 

fission product bioassay and potentially incomplete 

external dosimetry records.

 Dose reconstruction was determined to be feasible 

for the East site (EBR-II complex) as there was 

routine mixed fission product bioassay and air 

sample data indicating alpha exposures were 

controlled to less than 10% of the maximum 

permissible concentration (MPC).

Division of Compensation Analysis and Support
Health Endangerment

 Some workers in the class may have accumulated 

chronic radiation exposures through intakes of 

radionuclides at the EBR-I complex of ANL-W.

 NIOSH is therefore specifying that health may have 

been endangered for those workers monitored at ANL- W who were employed for a number of work days 

aggregating at least 250 work days.

 What about employees not included in the SEC?

 NIOSH intends to use monitoring data to conduct partial 

dose reconstructions for individuals not part of the SEC

Division of Compensation Analysis and Support
Proposed Class

All employees of the Department of Energy, its 

predecessor agencies, and their contractors and 

subcontractors who worked at the Argonne National 

Laboratory-West between April 10, 1951 and 

December 31, 1957 for a number of work days 

aggregating at least 250 work days, occurring either 

solely under this employment, or in combination with 

work days within the parameters established for one 

or more other classes of employees in the Special 

Exposure Cohort.

Division of Compensation Analysis and Support